Silicon grain refinement of zirconium

Abstract

 Substantially pure zirconium for use as a cladding material for nuclear fuel elements containing between about 40 ppm to about 120 ppm silicon and containing less Fe than its solubility limit in the zirconium.

Description

Field of the Invention

[0001] The present invention relates to the control of grain structure in unalloyed zirconium metal and, more particularly, to the control of grain structure in zirconium metals containing less than 300 parts per million Fe.

Background of the Invention

[0002] Zirconium tubing containing an outer layer of zirconium metal alloy and an inner layer of unalloyed zirconium metal is used extensively in nuclear power reactors and, in particular, in boiling water reactors.

[0003] The tubing is used to form a cladding to contain and support nuclear fuel pellets, usually made of uranium dioxide. The purpose of the pure or unalloyed zirconium liner is to reduce or prevent local chemical or mechanical interaction, or both, between the fuel pellets during the operation of the reactor and the more susceptible and more reactive outer zirconium alloy sheath. Such interactions between the fuel pellets and the cladding material is believed to be responsible for what is termed "iodine assisted stress corrosion cracking" of the outer zirconium alloy (Zircaloy) sheath. The resultant cracking of the sheath is deleterious to the safety of the reactor operation and to the lifetime of the fuel as it permits radioactive gaseous products of the fission reactions to diffuse therethrough and escape into the reactor vessel as well as permitting water or steam to contact the fuel elements directly.

[0004] The current accepted solution to the problem of iodine assisted stress corrosion cracking of zirconium alloys is the expedient of providing the structural zirconium alloy with an internal liner of substantially pure zirconium. This relatively inert unreactive liner provides the ductility required to prevent the pellet-­cladding interactions described.

[0005] The success of such liners has prompted most manufacturers to specify pure or substantially pure zirconium liners for the cladding inner tube liner. As a consequence, lower levels of oxygen and iron impurities are being tolerated. This has created a secondary problem of major concern.

[0006] As zirconium is rendered purer, the metallurgical grain size of the zirconium in the liner tends to increase. Normally impurities such as iron when present in amounts above its solubility limit in zirconium tend to pin grain boundaries in place during the thermal processing required in the manufacture of the liner if the iron is present as a finely dispersed intermetallic second phase. Moreover, as the grain size increases, secondary grain growth occurs which contributes to the formation of a non-uniform bi-modal grain size distribution where many smaller grains co-exist with many larger grains. This bi-­modal or duplex distribution creates problems during the subsequent fabrication processing for making barrier tube shells into finished tubing.

[0007] Normally a zirconium alloy tube mated to an unalloyed zirconium tube are tube reduced in a Pilger mill which reduces the size of the tube to the eventual size of the combination for its cladding function. When the purity of the zirconium liner has reduced the pinning function of some impurities and a bi-modal grain distribution has formed, local microcracking begins to occur at the grain boundaries between the clusters of large and small grains. It is believed that the local deformation inhomogeneities present between clusters or aggregates of large grains and aggregates or clusters of small grains, causes the zirconium to respond differently to deformation induced straining. It appears that the stresses created in the tube reducing operation can exceed the cohesive strength of the grain boundaries. The resultant microcracks, if numerous or deep enough, will significantly reduce the liner's ability to prevent the local pellet-cladding interactions previously described.

[0008] It is therefore an objective of the present invention reduce the occurrence of microcracking at grain boundaries in relatively pure zirconium fuel cladding liner material.

[0009] It is a further objective of the present invention to produce uniformly sized relatively small grain sizes in zirconium cladding liner materials containing less than 300 parts per million of iron impurities.

[0010] It is a further object of the present invention to provide a method for preventing the formation of bi-modal grain size distributions in unalloyed zirconium to be used as fuel cladding liner material.

[0011] It is a further object of the present invention to provide a coextruded nuclear fuel cladding comprising an outer zirconium alloy tube bonded to an inner relatively pure unalloyed zirconium liner which can be fabricated by conventional mill practices and continue to exhibit superior resistance to deleterious fuel pellet cladding interactions.

Brief Summary of the Invention

[0012] Uniform small diameter grain sizes are achieved in relatively pure zirconium containing generally less than about 250 to 300 parts per million of Fe, or in amounts below its solubility limit in Zirconium, by the addition of small amounts of silicon to the zirconium compacts during electrode formation for subsequent vacuum arc melting to produce zirconium ingots. Preferably silicon is added in amounts of from about 40 parts per million to about 120 parts per million and most preferably in amounts of about 60 to about 90 parts per million to achieve the objects and advantages described herein.

Brief Description of the Drawings

[0013] 

Figure 1 is a graph of average grain diameter vs. annealing temperature at constant time from a range of iron and silicon in unalloyed zirconium.

Figure 2 is a graph of average grain diameter for different concentrations of Silicon in zirconium for unquenched billets and beta quenched billets.

Detailed Description of the Invention

[0014] Silicon is known to be a potent grain refiner for a variety of metals including iron, titanium and aluminum as well as zirconium. The atomistic nature of grain refinement in zirconium is believed to occur because silicon combines with zirconium to form a tetragonal crystal structure, Zr₃Si. Precipitation of extremely fine (less than 10⁻⁶m) zirconium silicide (Zr₃Si) particles occurs during cooling from the beta or body center cubic phase of zirconium. These fine Zr₃Si precipitates serve to retard grain boundary movement. By doing this, grain growth is retarded and secondary recrystallization is prevented. The grains follow the classical log-normal size vs. frequency distribution when their boundaries have been pinned or locked into place by the Zr₃Si precipitates. Because clusters of large and small grains are not adjacent to each other, the formation of large strains at grain boundaries during cold deformation does not occur. In the absence of these localized strains, the zirconium liner material deforms uniformly and without cracking at the grain boundaries.

[0015] In the production of a barrier tube shell for nuclear reactor fuel cladding there is an external layer of zirconium alloy and an internal or barrier layer of unalloyed zirconium. In accordance with well conventional practice an ingot of zirconium alloy (typically Zircaloy 2) is press forged, rotary forged, machined into billets and beta quenched into water from about 1050-1150°C. An ingot of unalloyed zirconium is produced by multiple vacuum arc melting and is press forged and rotary forged into logs. The logs are machined into billets with an internal hole bored down the central axis, the length of the billet. The zirconium billets are extruded in the alpha temperature range into tubes. The extruded zirconium tube is cut to length and machined to fit a central hole bored through the Zircaloy billet. The liner tube and Zircaloy billet are cleaned, assembled and welded together. The assembled billet and liner tube are heated into the alpha range (600°C to 700°C) and coextruded into a barrier tubeshell. During coextrusion the barrier layer becomes intimately bonded to the Zircaloy substrate. The coextruded tubeshells are then annealed in the alpha range and can then be subjected to a series of cold reduction steps alpha annealing treatments, typically using a Pilger mill. Thus, the final size fuel cladding is achieved.

[0016] The addition of small quantities of silicon in the range of 40-120 ppm (and preferably between about 60 to about 90 ppm) is readily accomplished during ingot electrode makeup. Homogeneity of the silicon within the finished ingot is assured by multiple vacuum arc melting.

[0017] Uniform fine grain size is achieved by multiple cold reductions followed by recrystallization anneals. Annealing is limited to a temperature of less than 700°C for 2 hrs. and preferably in the range of from 620°C to 675°C to less than 650°C for 1 hr. The grain size of coextruded zirconium liner thus treated has an ASTM grain size of 9.5 to 11.

[0018] Advantages of the current invention include achieving a uniform fine grain size while controlling overall level of impurities (especially iron) to a much lower level than previously employed or than required by some proposed practices described in German Patent Application DE 3609074A1 filed March 18, 1986 by Daniel Charquet and Marc Perez. Additionally, no further special heat treatments or quenching operations are required to ensure the effectiveness of the silicon addition. Because no additional process steps are required, the manufacturing costs are not increased over conventional practice.

[0019] A number of experiments were conducted to evaluate the effectiveness of silicon for the current application. The first series of experiments consisted of arc melting 250 grams buttons of pure zirconium with intentional additions of iron and silicon to compare the effectiveness of silicon vs. iron. The iron levels varied from 215 ppm to 1240 ppm. Silicon was added at the 90 ppm level to a low iron (245 ppm Fe) button. The buttons were remelted into small rectangular ingots which were then hot rolled to an intermediate thickness of 0.2". The hotband thus produced was vacuum annealed at 625°C for 2 hrs. The annealed hotband was cold rolled to 0.1" thick and again vacuum annealed at 625°C for 2 hrs. The strip was further cold rolled to 0.040" thick. Vacuum or air final anneals were preformed over the ranges of 500°C to 700°C and 0.1 hr to 10 hrs. All specimens were metallographically prepared and photomicrographs were obtained. From the photomicrographs, a lien intercept counting technique was used to determine average grain diameter in micrometers. Figure 1 displays a plot of average grain diameter vs. annealing temperature (annealing time 2 hrs.) for the range of iron and silicon compositions mentioned above. One can see that in the non-quenched condition, the sample containing 92 ppm Si and 245 ppm Fe has a smaller grain size than does the sample with the highest iron level of 1240 ppm.

[0020] A second experiment was conducted to investigate the effect of varying levels of silicon on grain size. A number of buttons were melted to give a range of silicon from 12 ppm to 94 ppm. The buttons were drop cast into rectangular ingots, hot rolled, annealed, cold rolled and final annealed at 625°C for 0.1-10 hrs., as in the first experiment. The average grain diameter for a 625°C-10 hr. final anneal was obtained and is shown in Figure 2 plotted against the silicon content. Additionally, at the 0.2" thickness the hotband was split into two equal quantities and one half was beta quenched while the other half was not. Based on Figure 2, the optimum level of silicon is greater than 40 ppm and less than 100 ppm with most grain refinement occurring by about 60 ppm. Beta quenching of zirconium containing less than 300 ppm iron was found to have no effect on the efficacy of the silicon's grain refining ability.

[0021] A third experiment was conducted, whereby the laboratory experiments were scaled up into a production sized environment. A 14" diameter pure Zr liner ingot was produced to the chemistry shown in Table 1. Notice that the silicon addition is aimed at 60 ppm and iron is intentionally kept at about 300 ppm or below. Preferably the iron-silicon was added as ferrosilicon. The ingot was forged to 7 1/2" diameter and sawed into extrusion billet lengths. One billet was beta solution treated (900-950°C for 3-4 minutes) and water quenched. A second billet did not receive this treatment. Both billets were extruded in the alpha phase at 700°C maximum furnace set temperature. Zircaloy 2 billets were prepared by forging, machining, induction beta quenched and final machined to receive the finished liners according to current state-of-the-art.

[0022] The two coextrusion billets were assembled, welded, coextruded to 2.5" OD x 0.44" wall tubeshells. The tubeshells were vacuum annealed at 620°C for 60 minutes. Liner samples were obtained from the lead and tail ends of the coextruded tubeshell. The grain size was measured and is shown in Table II.

[0023] Thus, barrier tubeshell made in accordance with standard production procedures and incorporating 60 ppm silicon shows a fine uniform grain size of 8.2 micrometers or less. Measurements made on liner grain size from production material without silicon additions shows an average grain size of 16 micrometers. Moreover, the silicon bearing liner microstructure shows no evidence of secondary recrystallization as evidenced by a duplex grain size distribution.

Table 1

Heat 355838 Ingot Chemistry
Zr Liner Ingot 13.7"o x 21.8" L x 730 lbs.
A1	<20	<20	<20
B	<.25	<.25	<.25
C	50	50	50
Ca	<10	<10	<10
Cd	<.25	<.25	<.25
Cl	<5	<5	<5
Co	<10	<10	<10
Cr	<50	<50	<50
Cu	<10	<10	<10
Fe	310	285	300
H	<5	<5	<5
Hf	57	59	54
Mg	<10	<10	<10
Mn	<25	<25	<25
Mo	<10	<10	<10
N	42	23	27
Na	<5	<5	<5
Nb	<50	<50	<50
Ni	<35	<35	<35
O	500	490	460
P	7	6	6
Pb	<25	<25	<25
Si	62	57	61
Sn	<10	<10	<10
Ta	<50	<50	<50
Ti	<25	<25	<25
U	<1.0	<1.0	<1.0
V	<25	<25	<25
W	<25	<25	<25

Table II

	Lead End	Trail End
Beta Quenched	10 1/2 (8.2 m)	11 1/2 (5.8 m)
Non-quenched	10 1/2 (8.2 m)	11 (6.9 m)

[0024] The nature of this invention is such that it would be applicable to other zirconium or zirconium alloy product forms. Specifically, commercially pure zirconium, referred to as UNS Grade R60702, would benefit from the grain refining effects of silicon at the upper levels (100-120 ppm) of the current invention. The finer grained, more homogeneous product thus produced would lend itself to improving formability, specifically of sheet parts.

[0025] The invention has been described by reference to the present preferred embodiments thereof. Variations in compositions and processing conditions may be employed within the spirit and scope of the inventive concepts described herein. The invention should, therefore, only be limited by the scope of the appended claims interpreted in light of the pertinent prior art.

Claims

1. Substantially pure zirconium for use as a cladding material for nuclear fuel elements containing between about 40 ppm to about 120 ppm silicon and containing less Fe than its solubility limit in the zirconium.

2. The zirconium of claim 1 wherein the average final ASTM grain size is less than about 11.

3. A coextruded cladding element containing an outer zirconium alloy shell bonded to a substantially pure zirconium inner shell liner wherein said inner shell liner and said outer shell are extruded together and then vacuum annealed at a temperature of about 620°C for about 20 minutes.

4. The coextruded cladding element of claim 3 wherein said inner shell liner is extruded in the alpha phase at a temperature of about 700°C before coextrusion together with said outer zirconium alloy shell.

5. The coextruded cladding element of claim 4 wherein said inner shell liner is solution treated in the beta phase at a temperature of from about 900°C to about 950°C and water quenched before extrusion in the alpha phase.

6. A method of making a two component cladding element for containing nuclear fuel wherein an outer shell of said element consists essentially of a zirconium alloy and the inner shell of said element consists of unalloyed zirconium tube coextruded together with said outer alloy shell to form a unitary article, comprising the steps of
forming an outer tube billet of zirconium alloy of preselected dimensions; heating said alloy to a temperature in the beta phase and quenching said alloy,
forming a tube of unalloyed zirconium of preselected dimensions obtained by extrusion at a temperature in the alpha phase, said preselected dimensions being such that said unalloyed zirconium tube fits snugly inside of said zirconium alloy tube forming an interface therebetween,
coextruding said tube and said billet to form a unitary cladding tube.

7. The method of claim 6 wherein the unitary cladding tube is annealed under vacuum at a temperature of from about 600°C to about 700°C to recrystallize said zirconium and zirconium alloy for further cold working conditions, said unalloyed zirconium liner of coextruded unitary cladding tube being characterized by containing between about 40 ppm and about 120 ppm silicon and less than about 300 ppm Fe and exhibiting a fine uniform grain size of less than about 7 micrometers.

Drawing